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| {{#Wiki_filter:}} | | {{#Wiki_filter:. |
| | . WESTINGHOUSE PROPRIETARY CLASS 3 , |
| | Supplementary Information to WCAP-10585, Technical Bases for Eliminating large Primary Loop Pipe Rupture on the Structural Design |
| | ! Basis for McGuire Units 1 and 2 J |
| | December 1985 |
| | ; S. A. Swamy F. J. Witt L |
| | APPROVED: |
| | J.IN. t bAID 11rigos, Mai49eJ/ |
| | APPROVED: |
| | E. R. Johnson, Manager Structural Materials i* Structural and Seismic Engineering Development APPROVED: 1 kbm J. '3! ~McVerney, Manaig Mechanical Equipment ahd i Systems Licensing , |
| | i i i |
| | I WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems P.O. Box 355 Pittsburgh, Pennsylvania 15230 l |
| | 0601240342 e60116 DR ADOCK 0 % g9 |
| | |
| | f DETERMINATION OF J APPLIED R MIRE UW 12 2 In WCAP-10585 (Technical Basis for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for McGuire Units 1 and 2), a |
| | ; comparison was made between the critical pipe section of the McGuire loop and j the generic pipe section analyzed in WCAP-9558, Revision 2. The generic loop section was found to envelope the McGuire piping. However, such an |
| | : enveloping evaluation provides little insight for margin analyses. Thus it became necessary to perform analyses and evaluations more typical of the McGuire piping. Specifically, the followirg analyses were performed. |
| | i 1. Adopting a yield stress of [ Ja ,c eksi for the aged piping material" of the McGuire plants and a tangent modulus of ( 38 'c eksib , ,pgp, similar to that in WCAP-9558, Revision 2, was analyzed for 8 'C'' |
| | circurferential through wall cracks of 7.5 and [ 3 inches. |
| | : 2. To account for small differences in gemetry, J is plotted versus the elastica 11y calculated axial stress instead of J versus moment as was done in WCAP-9558, Revision 2. |
| | J versus outer fiber axial stress for the two fir. sizes are given in Figures 1 and 2. As may be seen, for a stress of 26.70 ksi, J is around |
| | ! [ la,c,ein-lb/in 2for a 7.5 inch flaw, and around [ la c.ein-Ib/in2 for a[ Ja,c.eirich flaw. Thusly, was margin in flaw size established. |
| | * The code mininan yield of the unaged material at the critical location in WCAP-10585 is 21.2 ksi. |
| | b 8 In WCAP-9558, Revision 2, the yield stress was [ 3 'c.eksi and the tangent modulus of the 2nd part of the multilinear stress strain diagran was [ 38 '*''ksi (see Figure 3 1, page 3-9 of WCAP-9558, Revision 2) l l |
| | l f |
| | - . . - - . . . , - ,.- . --- --.--- - - . , - . - ~ ~ . - - . - - , - - - - . - . _ . - . , - , , - - . .- |
| | |
| | o - |
| | i ,- |
| | ,8,C, i |
| | l I |
| | i |
| | , e o |
| | i 1 |
| | t I I' |
| | i t |
| | i Figure 1 J versus the outer fiber axial stress for a [ |
| | wall circumferential flaw ]a.c.e inch long through l |
| | l l |
| | |
| | 2 |
| | .a,c.e l |
| | ? |
| | I i |
| | I Figure 2 J versus the outer fiber axial stress for a [ 3a,c.c inch long through wall circumferential flaw}} |
Revision as of 22:50, 30 June 2020
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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20202D1921997-12-31031 December 1997 Rev 2 to UFSAR Chapter 15 Transient Analysis Methodology ML20197J3011997-11-30030 November 1997 Non-proprietary TR DPC-NE-3004-A, Mass & Energy Release & Containment Response Methodology ML20248L2631997-02-20020 February 1997 Non-proprietary Version of DPC-NE-2004-A, Duke Power Co McGuire & Catawba Nuclear Stations Core Thermal-Hydraulic Methodology Using VIPRE-01 ML20108D2091996-04-30030 April 1996 Nonproprietary App C, Mcguire/Catawba Plant Specific Data Mark-BW Fuel BWU-Z CHF Correlation to DPC Thermal- Hydraulic Statistical Core Design Methodology ML20107M8931995-10-31031 October 1995 Nonproprietary DPC Fuel Reconstitution Analysis Methodology ML20073J9151994-09-19019 September 1994 Replacement Steam Generator Topical Rept ML20070K0711994-06-30030 June 1994 Rev 1 to FSAR Chapter 15 Sys Transient Analysis Methodology ML20065D8061994-02-28028 February 1994 Analysis of Capsule V Specimens & Dosimeters & Analysis of Capsule Z Dosimeters from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program ML20064M4521994-02-28028 February 1994 WCAP-13948, Evaluation of Pressurized Thermal Shock for McGuire Unit 1 ML20116N0531992-11-11011 November 1992 Rev 1 to Mark-BW Reload LOCA Analysis for McGuire & Catawba ML20114A9771991-12-31031 December 1991 Nonproprietary McGuire & Catawba Nuclear Stations Core Thermal-Hydraulic Methodology Using VIPRE-01 ML20114A9911991-11-30030 November 1991 Nonproprietary Multidimensional Reactor Transients & Safety Analysis Physics Parameters Methodology ML20114A9711991-11-30030 November 1991 FSAR Chapter 15 Sys Transient Analysis Methodology ML20065M7381990-11-30030 November 1990 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units ML20073H6281990-01-31031 January 1990 Nonproprietary Topical Rept DPC-NE-2001-A, Fuel Mechanical Reload Analysis Methodology for Mark-BW Fuel, Rev 1 ML20011E2541989-12-31031 December 1989 ARROTTA-HERMITE Code Comparison, Final Rept ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. ML20042F2321989-08-31031 August 1989 Nonproprietary DCHF-1 Correlation for Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies. ML19332C1531989-08-31031 August 1989 Analysis of Capsule X from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program. ML20235M9111989-02-20020 February 1989 Nonproprietary Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue ML20207L7781988-10-0606 October 1988 Nonproprietary WCAP 11936, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue ML20207L9261988-09-30030 September 1988 Nonproprietary Addendum 2 to COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment (Response to NRC Questions) ML20212B8841986-07-31031 July 1986 Nonproprietary Tubesheet Region Plugging Criterion for Duke Power Co McGuire Nuclear Station Units 1 & 2 Steam Generators ML20137L0591985-12-31031 December 1985 Nonproprietary Supplementary Info to WCAP-10585, Technical Bases for Eliminating Large Primary Loop Pipe Rupture on Structural Region Bases for McGuire Units 1 & 2 ML20127K1381985-06-30030 June 1985 Nuclear Physics Methodology for Reload Design ML20100H4581985-02-28028 February 1985 Analysis of Capsule U from Duke Power Co McGuire Unit 1 Reactor Vessel Radiation Surveillance Program ML20093N0811984-10-19019 October 1984 App a to Topical Rept DPC-NF-2010, Code Summary ML20135E2691984-06-30030 June 1984 Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Bases for McGuire Units 1 & 2 ML20092N5761984-06-30030 June 1984 Nonproprietary Technical Basis for Eliminating RHR Line Rupture as Structural Design Basis for Catawba Units 1 & 2 & McGuire Units 1 & 2 ML20078C2411983-07-31031 July 1983 Nonproprietary Preliminary Version of McGuire Post-Mod Steam Generator Tube Vibration Monitoring Program ML19331C6921980-07-31031 July 1980 Reliability Analysis of Auxiliary Feedwater Sys for McGuire Nuclear Station Unit 1. 1999-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C8911999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9021999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20204C8961999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2 ML20199E0301998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20198D7561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199E0491998-11-30030 November 1998 Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20196D4171998-11-24024 November 1998 Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress ML20196G0581998-11-0606 November 1998 Rev 17 to COLR Cycle 13 for McGuire Unit 1 ML20196G0761998-11-0606 November 1998 Rev 15 to COLR Cycle 12 for McGuire Unit 2 ML20198D7771998-10-31031 October 1998 Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E5961998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154L6251998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E6021998-09-30030 September 1998 Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154B4131998-09-22022 September 1998 Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage ML20151W3521998-09-0808 September 1998 Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc ML20154L6321998-08-31031 August 1998 Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1 ML20153B3741998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20237B2381998-07-31031 July 1998 Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2 ML20153B3931998-07-31031 July 1998 Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days 1999-09-30
[Table view] |
Text
.
. WESTINGHOUSE PROPRIETARY CLASS 3 ,
Supplementary Information to WCAP-10585, Technical Bases for Eliminating large Primary Loop Pipe Rupture on the Structural Design
! Basis for McGuire Units 1 and 2 J
December 1985
- S. A. Swamy F. J. Witt L
APPROVED:
J.IN. t bAID 11rigos, Mai49eJ/
APPROVED:
E. R. Johnson, Manager Structural Materials i* Structural and Seismic Engineering Development APPROVED: 1 kbm J. '3! ~McVerney, Manaig Mechanical Equipment ahd i Systems Licensing ,
i i i
I WESTINGHOUSE ELECTRIC CORPORATION Nuclear Energy Systems P.O. Box 355 Pittsburgh, Pennsylvania 15230 l
0601240342 e60116 DR ADOCK 0 % g9
f DETERMINATION OF J APPLIED R MIRE UW 12 2 In WCAP-10585 (Technical Basis for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for McGuire Units 1 and 2), a
- comparison was made between the critical pipe section of the McGuire loop and j the generic pipe section analyzed in WCAP-9558, Revision 2. The generic loop section was found to envelope the McGuire piping. However, such an
- enveloping evaluation provides little insight for margin analyses. Thus it became necessary to perform analyses and evaluations more typical of the McGuire piping. Specifically, the followirg analyses were performed.
i 1. Adopting a yield stress of [ Ja ,c eksi for the aged piping material" of the McGuire plants and a tangent modulus of ( 38 'c eksib , ,pgp, similar to that in WCAP-9558, Revision 2, was analyzed for 8 'C
circurferential through wall cracks of 7.5 and [ 3 inches.
- 2. To account for small differences in gemetry, J is plotted versus the elastica 11y calculated axial stress instead of J versus moment as was done in WCAP-9558, Revision 2.
J versus outer fiber axial stress for the two fir. sizes are given in Figures 1 and 2. As may be seen, for a stress of 26.70 ksi, J is around
! [ la,c,ein-lb/in 2for a 7.5 inch flaw, and around [ la c.ein-Ib/in2 for a[ Ja,c.eirich flaw. Thusly, was margin in flaw size established.
- The code mininan yield of the unaged material at the critical location in WCAP-10585 is 21.2 ksi.
b 8 In WCAP-9558, Revision 2, the yield stress was [ 3 'c.eksi and the tangent modulus of the 2nd part of the multilinear stress strain diagran was [ 38 '*ksi (see Figure 3 1, page 3-9 of WCAP-9558, Revision 2) l l
l f
- . . - - . . . , - ,.- . --- --.--- - - . , - . - ~ ~ . - - . - - , - - - - . - . _ . - . , - , , - - . .-
o -
i ,-
,8,C, i
l I
i
, e o
i 1
t I I'
i t
i Figure 1 J versus the outer fiber axial stress for a [
wall circumferential flaw ]a.c.e inch long through l
l l
2
.a,c.e l
?
I i
I Figure 2 J versus the outer fiber axial stress for a [ 3a,c.c inch long through wall circumferential flaw